公开(公告)号：US08172959B2

公开(公告)日：2012-05-08

申请号：US10585885

申请日：2005-01-13

申请人： Yasuhiro Sakaguchi ,  Toshihiko Iwamura ,  Hiroshi Kanasaki ,  Hidehito Mimaki ,  Masaki Taneike ,  Shunichi Suzuki ,  Kenrou Takamori ,  Suguru Ooki ,  Naoki Anahara ,  Naoki Hiranuma ,  Toshio Yonezawa

发明人： Yasuhiro Sakaguchi ,  Toshihiko Iwamura ,  Hiroshi Kanasaki ,  Hidehito Mimaki ,  Masaki Taneike ,  Shunichi Suzuki ,  Kenrou Takamori ,  Suguru Ooki ,  Naoki Anahara ,  Naoki Hiranuma ,  Toshio Yonezawa

IPC分类号： C22C38/44 ,  C21D8/10 ,  C21D9/08

CPC分类号： C21D6/002 ,  C21D6/001 ,  C21D6/004 ,  C21D6/02 ,  C21D7/02 ,  C21D2211/001 ,  C22C38/001 ,  C22C38/02 ,  C22C38/04 ,  C22C38/44 ,  Y10S376/90 ,  Y10T428/13

摘要： There are provided an austenitic stainless steel having high stress corrosion crack resistance, characterized by containing, in percent by weight, 0.030% or less C, 0.1% or less Si, 2.0% or less Mn, 0.03% or less P, 0.002% or less S, 11 to 26% Ni, 17 to 30% Cr, 3% or less Mo, and 0.01% or less N, the balance substantially being Fe and unavoidable impurities; a manufacturing method for an austenitic stainless steel, characterized in that a billet consisting of the said austenitic stainless steel is subjected to solution heat treatment at a temperature of 1000 to 1150° C.; and a pipe and a in-furnace structure for a nuclear reactor to which the said austenitic stainless steel is applied.

摘要翻译： 提供了具有高应力腐蚀开裂性的奥氏体不锈钢，其特征在于，以重量％计含有C：0.1％以下，C：0.1％以下，2.0％以下的Mn，0.03％以下的P，0.002％以下 较少的S，11〜26％的Ni，17〜30％的Cr，3％以下的Mo和0.01％以下的N，余量基本上是Fe和不可避免的杂质; 一种奥氏体不锈钢的制造方法，其特征在于，将由所述奥氏体不锈钢构成的坯料在1000〜1150℃的温度下进行固溶热处理。 以及用于所述奥氏体不锈钢的核反应堆的管和炉内结构。

公开(公告)号：US20080308198A1

公开(公告)日：2008-12-18

申请号：US10585885

申请日：2005-01-13

申请人： Yasuhiro Sakaguchi ,  Toshihiko Iwamura ,  Hiroshi Kanasaki ,  Hidehito Mimaki ,  Masaki Taneike ,  Shunichi Suzuki ,  Kenrou Takamori ,  Suguru Ooki ,  Naoki Anahara ,  Naoki Hiranuma ,  Toshio Yonezawa

发明人： Yasuhiro Sakaguchi ,  Toshihiko Iwamura ,  Hiroshi Kanasaki ,  Hidehito Mimaki ,  Masaki Taneike ,  Shunichi Suzuki ,  Kenrou Takamori ,  Suguru Ooki ,  Naoki Anahara ,  Naoki Hiranuma ,  Toshio Yonezawa

IPC分类号： C21D8/00 ,  C22C38/44 ,  C22C38/58 ,  B32B1/02 ,  C21D1/00

CPC分类号： C21D6/002 ,  C21D6/001 ,  C21D6/004 ,  C21D6/02 ,  C21D7/02 ,  C21D2211/001 ,  C22C38/001 ,  C22C38/02 ,  C22C38/04 ,  C22C38/44 ,  Y10S376/90 ,  Y10T428/13

摘要： There are provided an austenitic stainless steel having high stress corrosion crack resistance, characterized by containing, in percent by weight, 0.030% or less C, 0.1% or less Si, 2.0% or less Mn, 0.03% or less P, 0.002% or less S, 11 to 26% Ni, 17 to 30% Cr, 3% or less Mo, and 0.01% or less N, the balance substantially being Fe and unavoidable impurities; a manufacturing method for an austenitic stainless steel, characterized in that a billet consisting of the said austenitic stainless steel is subjected to solution heat treatment at a temperature of 1000 to 1150° C.; and a pipe and a in-furnace structure for a nuclear reactor to which the said austenitic stainless steel is applied.

摘要翻译： 提供了具有高应力腐蚀开裂性的奥氏体不锈钢，其特征在于，以重量％计含有C：0.1％以下，C：0.1％以下，2.0％以下的Mn，0.03％以下的P，0.002％以下 较少的S，11〜26％的Ni，17〜30％的Cr，3％以下的Mo和0.01％以下的N，余量基本上是Fe和不可避免的杂质; 一种奥氏体不锈钢的制造方法，其特征在于，将由所述奥氏体不锈钢构成的钢坯在1000〜1150℃的温度下进行固溶热处理。 以及用于所述奥氏体不锈钢的核反应堆的管和炉内结构。

公开(公告)号：US5976275A

公开(公告)日：1999-11-02

申请号：US836519

申请日：1997-06-05

申请人： Toshio Yonezawa ,  Toshihiko Iwamura ,  Hiroshi Kanasaki ,  Koji Fujimoto ,  Shizuo Nakada ,  Kazuhide Ajiki ,  Mitsuhiro Nakamura

发明人： Toshio Yonezawa ,  Toshihiko Iwamura ,  Hiroshi Kanasaki ,  Koji Fujimoto ,  Shizuo Nakada ,  Kazuhide Ajiki ,  Mitsuhiro Nakamura

IPC分类号： G21D1/00 ,  C21D6/00 ,  C21D8/00 ,  C22C30/00 ,  C22C38/00 ,  C22C38/44 ,  C22C38/54 ,  C22C38/302

CPC分类号： C22C30/00 ,  C21D6/004 ,  C22C38/44 ,  C21D8/005

摘要： The present invention aims at providing structural materials having a resistance to degradation by neutron irradiation, causing no SCC in an environment of light-water reactors even after subjecting the materials to neutron irradiation of approximately at least 1.times.10.sup.22 n/cm.sup.2 (E>1 MeV), and having thermal expansion coefficients approximately similar to that of structural materials. The high nickel austenitic stainless steels of the present invention having a resistance to degradation by neutron irradiation can be produced by subjecting stainless steels having compositions (by weight %) of 0.005 to 0.08% of carbon, at most 0.3% of Mn, at most 0.2% of (Si+P+S), 25 to 40% of Ni, 25 to 40% of Cr, at most 3% of Mo or at most 5% of (Mo+W), at most 0.3% of Nb+Ta, at most 0.3% of Ti, at most 0.001% of B and the balance of Fe to a solution-annealing treatment at a temperature of 1000 to 1150.degree. C.

摘要翻译： PCT No.PCT / JP96 / 02442 Sec。 371日期：1997年6月5日 102（e）日期1996年6月5日PCT提交1996年8月30日PCT公布。 公开号WO97 / 09456 日期1997年3月13日本发明旨在提供具有耐中子辐射降解性的结构材料，即使在使材料经受大约至少1×1022n / cm 2的中子照射之后也不会在轻水反应堆的环境中产生SCC（ E> 1 MeV），并且具有与结构材料大致相似的热膨胀系数。 具有耐中子辐射降解性的本发明的高镍奥氏体不锈钢可以通过将具有0.005-0.08％的碳，至多为0.3％Mn的组成（重量％）的不锈钢制成至多0.2 （Si + P + S），25〜40％的Ni，25〜40％的Cr，至多3％的Mo或至多5％的（Mo + W），至多0.3％的Nb + Ta ，至多0.3％的Ti，至多0.001％的B，余量为在1000至1150℃的温度下进行的溶液退火处理。

公开(公告)号：US06245163B1

公开(公告)日：2001-06-12

申请号：US09294738

申请日：1999-04-19

申请人： Toshio Yonezawa ,  Toshihiko Iwamura ,  Koji Fujimoto

发明人： Toshio Yonezawa ,  Toshihiko Iwamura ,  Koji Fujimoto

IPC分类号： C21D800

CPC分类号： C21D8/005 ,  C21D6/004 ,  C22C38/38 ,  C22C38/44

摘要： An austenitic stainless steel having resistance to neutron-irradiation-induced deterioration obtained by subjecting a stainless steel consisting of not more than 0.08% by weight of C, not more than 2.0% by weight of Mn, not more than 1.5% by weight of Si, not more than 0.045% by weight of P, not more than 0.030% by weight of S, 8.0 to 22.0% of by weight Ni, 16.0 to 26.0% of by weight Cr and the balance as Fe; to thermal solid solution treatment at a temperature of 1,000° C. to 1,180° C. and then subjecting the so-treated steel to aging treatment at a temperature in the range of 600° C. to 750° C.

摘要翻译： 具有耐中子辐照诱发劣化的奥氏体不锈钢，其通过使由不超过0.08重量％的C，不超过2.0重量％的Mn，不大于Si重量的1.5重量％的不锈钢 ，不大于0.045重量％的P，不大于0.030重量％的S，8.0至22.0重量％的Ni，16.0至26.0重量％的Cr，余量为Fe; 在1000℃至1180℃的温度下进行热固溶处理，然后在600℃至750℃的温度下对经过处理的钢进行老化处理。